ML20105B638
| ML20105B638 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/31/1992 |
| From: | Booker J, Egan J, Vo P GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20105B634 | List: |
| References | |
| EA-CA-92-0007-M, EA-CA-92-0007-M-R00, EA-CA-92-7-M, EA-CA-92-7-M-R, NUDOCS 9209210075 | |
| Download: ML20105B638 (17) | |
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EA-CA-92-0007-M Page 1 of 17 RBS CYCLE 5 COLR Rev. 0 RIVER BEND STATION, CYOLE 5 CORE OPERATING LIMITS REPORT (COLR) l AUGUST 1992 j
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PREPARED BY:
PH ll-Y N
DATEt.h/7 2.-
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ar/,..F els Engineer l
Br. N
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Sr. Nucleaf Safety Engineer' REVIEWED BY h-
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DATEt 3 2.[,71 Supervisor /
Thermal / Hydraulic-Analysis r
River Bend Nuclear Station
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APPROVED BY
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- CO 2' / l DATE: M hf/9 L s u'p e r v i s o r, c o r e A n a l y s i s River Bend Nuclear Station APPROVED BY -
rTSLI// (A -LATE: __
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l En sering Analysis I
River Bond Nuc,e r Station
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@['26 7L-Ngager, Engineer'ing River Bend, Nuclear Station-
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AlPROVED BY Facilities Review: Commit'tes River Band Nuclear. Station i
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APPRI'VED'BY
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9M9210075 920911'
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EA-CA-92-0007-M Page 2 of 17 RBS CYCLE 5 COLR Rev. 0 LIST OF EFFECTIVE PAQEg Page(s)
Revision 1-17 0
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j EA-CA-92-0007-M Page 3 of 17 l-RBS CYCLE 5 COLR i
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IllTRODUCTIOff AND SUtiMARY a
This report provides the values of the AVERAGE. PLANAR
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LINEAR HEAT GENERATIOli RATE (APLHGR) limits, the core ficw dependent MINIMUM CRITICAL POWER RATIO (MCPR) limits, MCPRr,
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I the thermal power dependent MCPR limits MCPR, the LINEAR HEAT p
GENERATION RATE (LHGR) limits, and the REACTOR PROTECTIOff SYSTEM (RPS) response time for APRM thermal time constant for River Bend
- Station, Cycle 5
as ' required. by Technical l.
Specification 6.9.3.1.
Per Technical Specifications 6.9.3.2
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and 6.9.3.3, these ' values have been determined using NRC-approved methodology and are established such that all j
applicable limits of the plant safety analysis are met.
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EA-CA-92-0007-M j
Page 4 of 17 j
e TECHNICAL SPECIFICATlQN 3.2 1 FOWER DISTRIBUTION LIMILS 4
AVERAGE PLANAR LINEAR HEAT GENERATIQLLRATE i
j The limiting APLHGR value for the most limiting lattice
{
(excluding natural uranium) of each fuel type as a function of j
AVERAGE PLANAR EXPOSURE is given in Figures 1, 2, 3, 4, 5, and i
6.
These values were determined witn the SAFE /REFLOOD LOCA i
methodology described in GESTAR-II- (Reference 1).
Core locatinn by fuel type is provided in Figure 9, which is taken
~
from Reference 3.
These. figurer. are used if alternate calculationn are required.
The limits of these figures shall j
be reduced-to a va'.ue of 0.84 times the two recirculation loop operation limit '< hen in single leap operation (Reference 4).
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s EA-CA-92-0007-M J
Page 5 of 17 i
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Rev. O IECHNICAL SPECIFICATION 3.2.3 j
POWER DISTRIJ)UTION LIMITS MINIMUM CRITICAL POWER RATIO i
The MCPR limits for use in Technical Specification 3.2.3 4
for MCPRfand MCPR are shown in Figures 7 and 8.
These values p
j were determined with the GEMINI methodology and GEXL-PLUS critical power ratio correlation described in GESTAR-II I
(Reference 1) and are consistent with a Safety Limit MCPR of 1.07.
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EA-CA-92-0007-M Page 6 of 17 RBS CYCLE 5 COLR j
Rev. 0 l
l TECHNICAL SPECIFICATION 3.2.4 POWER DISTRIBUTION LIMITS f
LINEAR HEAT GEEERATION RATE The LHGR limits for use in Technical Specification 3.2.4 are 14.4 kw/ft for GE8x8EB fuel and 13.4 kW/ft for all other fuel types.
The GE8x8EB fuel consists of fuel types GE8B-P8SQB322-8GZ-120M-4WR-150-T, GE8B-P8SQB322-9GZ-120M-4WR-150-T, j
GE8B-P85QB333-10GZ-120M-4WR-150-T, GE8B-P3SQB331-11GZ-120M-4WR-150-T and GE8B-P8SQB334-10GZ-120M-4WR-150-T.
Core location by fuel type is provided in Figure 9.
1 The higher limit for: GE8X8EB fuel.is proprietary to GE and does not appear in Reference 1.
The NRC SER on the GE8D i
design (Reference 2) recognizes the change to the LHGR limit, and the proprietary value is found in References 38 and 19 of i
l Reference 2.
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EA-CA-92-0007-M
- Page 7 of 17 RBS CYCLE 5 COLR Rev. 0 TECHNICAL SPECIFICATION _ TABLES 3.3.1-2 and 4."l.1.1-1 The simulated thermal power time constant for use in Technical Specification Table 3.3.1-2, Footnote ** is:
6 t 0.6 caconds.
The maximum simulated thermal power time constant for use in Technical specification surveillance Table 4.3.1.1-1 is:
6.6 seconds 4
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Page 8 of 17 RBS CYCLE 5 COLR Rev. O FEFERENCES 1)
NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel," (latest approved version).
2)
- Letter, C.O.
Thomas to J.S.
- Charnley, Acceptance for Ref erencing of Licenaing Topical Report," NEDE-24011-P-A-6, Amendment 10, General Electric Standard Application i
for Reload Fuel, May 28, 1985.
3)
Document
- 23A7181, Revision 0,
" Supplemental Reload-Licensing Report fr'r River Bend Station Reload 4,-Cycle 5," August 1992.
4)
" Single-Loop Operation Analysis for River' Bend Station, Unit 1," NEDO-31441, May 1987.
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MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXPOSURE BP3 SRB 299 r
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VERSUS AVERAGE PLANAR EXPOSURE GE8P P8SQB322 8GZ-120M-4WR 150 T l
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VERSUS AVERAGF PLANAR EXP07URE GE88 P8SQB322 9GZ 120M-4WR 150 T
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FIGURE 5 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)
VERSUS AVERAGE PLANAR EXFOSURE GE8B P8 SOB 331-11GZ-120M 4WR 150-T l
EA-C4-92 0007-M Page 14 of 17 RBS CYCLE 5 COLR Rev.0 14.00
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VERSUS AVERAGE PLANAR EXPOSURE GE8B P8SQB334-10GZ-120M-4WR 150 T
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Page 15 of 17 j
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-ENHHHHHL l
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EEEEEEEE IIIIIiiI 1 3 5 7 91113151719212325272931333537394143454749515355 (W.
FUEL TYPE A=GE88 P8508322 8GZ-120M 4WR-150 T 0 GE88 P8508331 11GZ-120M 4WR-!SO-T B GE88 P85Q8322 9GZ 120M 4WR-150-T E.8P85R8299 i
C=GE88 P8508333-10GZ.120M 4WR 150-T F.GE88 P85Q8334 10GZ-120M 4WR-150 T j
Figure 9.
Reference Core Loading Pattern 1